You need JavaScript to view this

Test apparatus for ITER blanket cooling water distributor design

Technical Report:

Abstract

Current Japanese breeding blanket concept being developed for the ITER driver blanket is comprised of three breeding layers, nine multiplier layers and five water cooling panels. In order to meet design requirements of tritium release efficiency and material temperature restrictions, configuration of these layers should be designed to achieve optimum temperature profiles in the radial direction of the blanket. Such temperature conditions are attained by appropriate water flow rate distribution in each cooling panel. Furthermore, the cooling panel must be designed to accommodate variation of D-T burning plasma density during ITER operation. We have developed an engineering test apparatus composed of three parallel cooling panel models. It was designed to examine performance of orifice type passive distributions for cooling header design. The apparatus can be operated under ITER blanket design conditions: temperature range; 60 - 100degC, water pressure; 1.5MPa, flow rate; 0.5-5m/s, pressure drop; up to 50kPa, heat flux of heater; 20-2000kW/m{sup 2}. (author).
Authors:
Yoshida, Hiroshi; Enoeda, Mikio; [1]  Hirata, Shingo; Ito, Hideki
  1. Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment
Publication Date:
May 01, 1992
Product Type:
Technical Report
Report Number:
JAERI-M-92-070
Reference Number:
SCA: 700450; PA: JPN-92:011078; SN: 93000918483
Resource Relation:
Other Information: PBD: May 1992
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ITER TOKAMAK; BREEDING BLANKETS; TRITIUM RECOVERY; LITHIUM OXIDES; WATER; SPECIFICATIONS; COOLING SYSTEMS; 700450; BLANKETS AND COOLING SYSTEMS
OSTI ID:
10111114
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE93753157; TRN: JP9211078
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
55 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Yoshida, Hiroshi, Enoeda, Mikio, Hirata, Shingo, and Ito, Hideki. Test apparatus for ITER blanket cooling water distributor design. Japan: N. p., 1992. Web.
Yoshida, Hiroshi, Enoeda, Mikio, Hirata, Shingo, & Ito, Hideki. Test apparatus for ITER blanket cooling water distributor design. Japan.
Yoshida, Hiroshi, Enoeda, Mikio, Hirata, Shingo, and Ito, Hideki. 1992. "Test apparatus for ITER blanket cooling water distributor design." Japan.
@misc{etde_10111114,
title = {Test apparatus for ITER blanket cooling water distributor design}
author = {Yoshida, Hiroshi, Enoeda, Mikio, Hirata, Shingo, and Ito, Hideki}
abstractNote = {Current Japanese breeding blanket concept being developed for the ITER driver blanket is comprised of three breeding layers, nine multiplier layers and five water cooling panels. In order to meet design requirements of tritium release efficiency and material temperature restrictions, configuration of these layers should be designed to achieve optimum temperature profiles in the radial direction of the blanket. Such temperature conditions are attained by appropriate water flow rate distribution in each cooling panel. Furthermore, the cooling panel must be designed to accommodate variation of D-T burning plasma density during ITER operation. We have developed an engineering test apparatus composed of three parallel cooling panel models. It was designed to examine performance of orifice type passive distributions for cooling header design. The apparatus can be operated under ITER blanket design conditions: temperature range; 60 - 100degC, water pressure; 1.5MPa, flow rate; 0.5-5m/s, pressure drop; up to 50kPa, heat flux of heater; 20-2000kW/m{sup 2}. (author).}
place = {Japan}
year = {1992}
month = {May}
}